Impact analysis of transport flasks
Creators
- 1. Principia Espana S.A., Madrid
- 2. Impell Corp., Warrington (UK)
Description
This paper presents a methodology, based on the computer programs NOVA2D and NOVA3D, for carrying out the dynamic non-linear analyses required for impact assessment of spent nuclear fuel transport flasks. The procedures implemented are able to treat both geometrical non-linearities (such as contact interfaces, large strains and rotations) and constitutive non-linearities (including non-linear strain hardening and strain-rate dependence). As an example, some analysis of a generic cylindrical flask are undertaken. The 9m drops onto unyielding targets are presented both for a flat-on-end drop (axisymmetric analysis) and for an edge drop (three-dimensional analysis). A 36m edge drop is also studied for comparison. It is concluded that the flat-on-end lid drop is not too far from elastic and leads to high decelerations for the flask internals, while the substantial localised plasticity induced in corner drops has a shock absorbing effect leading to much lower decelerations. (author)
Additional details
Publishing Information
- Publisher
- Cambridge University Press.
- Imprint Place
- Cambridge (UK)
- ISBN
- 0 521 35130 8
- Imprint Title
- Nuclear containment
- Imprint Pagination
- 457 p.
- Journal Page Range
- p. 256-266.
Conference
- Title
- International conference on nuclear containment.
- Dates
- 6-8 Apr 1987.
- Place
- Cambridge (UK).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 19095682
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CASKS; CONTAINMENT; CYLINDRICAL CONFIGURATION; FINITE DIFFERENCE METHOD; IMPACT SHOCK; IMPACT TESTS; N CODES; NONLINEAR PROBLEMS; SPENT FUELS; THREE-DIMENSIONAL CALCULATIONS; TIME DEPENDENCE
- Descriptors DEC
- COMPUTER CODES; CONFIGURATION; CONTAINERS; ENERGY SOURCES; FUELS; ITERATIVE METHODS; MATERIALS; MATERIALS TESTING; MECHANICAL TESTS; NUCLEAR FUELS; NUMERICAL SOLUTION; REACTOR MATERIALS; TESTING